Published July 1985 | Version v1
Report Open

Leak rate analysis of the Westinghouse Reactor Coolant Pump

Creators

Description

An independent analysis was performed by ETEC to determine what the seal leakage rates would be for the Westinghouse Reactor Coolant Pump (RCP) during a postulated station blackout resulting from loss of ac electric power. The object of the study was to determine leakage rates for the following conditions: Case 1: All three seals function. Case 2: No. 1 seal fails open while Nos. 2 and 3 seals function. Case 3: All three seals fail open. The ETEC analysis confirmed Westinghouse calculations on RCP seal performance for the conditions investigated. The leak rates predicted by ETEC were slightly lower than those predicted by Westinghouse for each of the three cases as summarized below. Case 1: ETEC predicted 19.6 gpm, Westinghouse predicted 21.1 gpm. Case 2: ETEC predicted 64.7 gpm, Westinghouse predicted 75.6 gpm. Case 3: ETEC predicted 422 gpm, Westinghouse predicted 480 gpm. 3 refs., 22 figs., 6 tabs

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A04/MF A01 - GPO as TI85901844.

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Additional details

Publishing Information

Imprint Pagination
64 p.
Report number
NUREG/CR--4294

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17013339
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COMPUTERIZED SIMULATION; FINITE ELEMENT METHOD; HIGH PRESSURE; HIGH TEMPERATURE; LEAKS; OUTAGES; PRIMARY COOLANT CIRCUITS; PUMPS; PWR TYPE REACTORS; REACTOR SAFETY; SEALS; SENSITIVITY ANALYSIS; STATISTICS; STRUCTURAL MODELS; TWO-PHASE FLOW
Descriptors DEC
COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLUID FLOW; MATHEMATICS; NUMERICAL SOLUTION; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
ETEC-DRF--1714.